ML18040A965: Difference between revisions

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{{#Wiki_filter:o'L t "(I a g, a t+a%+44 4+r  y Robert G. Byram                                  PP&L, Inc.                            ilke a Senior Vice President                    Two North Ninth Street Aw~
{{#Wiki_filter:o'L t "(I a g, a t+a%+44 4+r  y Robert G. Byram                                  PP&L, Inc.                            ilke a Senior Vice President                    Two North Ninth Street Aw~
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                                                                                                                                "
Generation and Chtet Nuclear Officer                Allentown, PA 18101-1179 Tel. 610.774.7502 Fax 610.774.5019                            Tel. 610.774.5151 E-mail:rgbyramepapl.corn                      http:I/www.ppl-inc.corn/
Generation and Chtet Nuclear Officer                Allentown, PA 18101-1179 Tel. 610.774.7502 Fax 610.774.5019                            Tel. 610.774.5151 E-mail:rgbyramepapl.corn                      http:I/www.ppl-inc.corn/
     ~gg ).g )999 U: S. Nuclear Regulatory Commission Attn.: Document Control Desk Mail Station P 1-137 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION ADDITIONALINFORMATIONRE PROPOSED AMENDMENTNO. 1S4 TO LICENSE NPF-22:
     ~gg ).g )999 U: S. Nuclear Regulatory Commission Attn.: Document Control Desk Mail Station P 1-137 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION ADDITIONALINFORMATIONRE PROPOSED AMENDMENTNO. 1S4 TO LICENSE NPF-22:

Latest revision as of 14:24, 3 February 2020

Submits Addl Info Re Proposed Amend 184 to License NPF-22 for ANFB-10 Critical Power Correlation & MCPR Safety Limits
ML18040A965
Person / Time
Site: Susquehanna Talen Energy icon.png
Issue date: 01/12/1999
From: Byram R
PENNSYLVANIA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18040A966 List:
References
PLA-5018, NUDOCS 9901210320
Download: ML18040A965 (2)


Text

o'L t "(I a g, a t+a%+44 4+r y Robert G. Byram PP&L, Inc. ilke a Senior Vice President Two North Ninth Street Aw~

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Generation and Chtet Nuclear Officer Allentown, PA 18101-1179 Tel. 610.774.7502 Fax 610.774.5019 Tel. 610.774.5151 E-mail:rgbyramepapl.corn http:I/www.ppl-inc.corn/

~gg ).g )999 U: S. Nuclear Regulatory Commission Attn.: Document Control Desk Mail Station P 1-137 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION ADDITIONALINFORMATIONRE PROPOSED AMENDMENTNO. 1S4 TO LICENSE NPF-22:

ANFB-10 CPC AND MCPR SAFETY LIMITS PLA-501S Docket No.'50-388

Reference:

PLA-4946, R. G. Byram to USNRC, "Proposed Amendment No. 184 to License NPF-22:

ANFB-10 Critical Power Correlation and MCPR Safety Limits, " dated August 4, 1998.

On January 11, 1999, a telephone conference was held between PP&L and V. Nerses and T. Huang of NRR to discuss the referenced proposed amendment. During that conference it was agreed that PP&L would docket the information provided below.

~ U2C10 Core Com osition Assembly Type Previous Cycle Number of Assemblies Operational History SPC Atrium'- 10 Fresh 280 SPC Atrium'- 10 Once-burned 312 SPC 9x9-2 Twice-burned GE 12 (LUA)- '. Twice=burned 168 4>>

Total 764 U2C10 will be the third and last cycle of operation for the GE 12 Lead Use Assemblies (LUA's). The first cycle was 18 months, the current one 24 months, and U2C10 will be 24 months, for a total planned residence time of 5.5 years. This is well within the maximum allowed residence time of 8 years.

~ U2C10 Sin le Loo Safe Limit The U2C10 Single Loop MCPR Safety Limit is calculated by Siemens Power Corporation (SPC) using the approved methodology referenced in Technical Specification Section 5.6.5. The U2C10 Single Loop MCPR Safety Limit was calculated by SPC to be 1.12. The cycle-specific SPC calculated fraction of fuel rods in boiling transition for this value is 0.086%. SPC utilized 1000 monte carlo trials in this Safety Limitevaluation.

PLA-5018 Document Control Desk

~ Editorial Revision to Pro osed Reference 19 A

Attached is a marked up page revising the referenced submittal to reflect the final approved version of the reports noted in proposed Refer'ence 19. These final versions, which contain the same information as the originally proposed reference, were not published at the time of our August 4, 1998 submittal. Since this change is purely editorial, no revision is required to our previous Safety Assessment, No Significant Hazards Considerations, or Environmental Assessment.

Any questions on this information should be directed to Mr. R. Sgarro at (610) 774-7552.

Sincerely, R. G. Byram Attachment Copy: NRC Region I Mr. V. Nerses, NRC Sr. Project Manager OWFN Mr. S. L. Hansell Jr., NRC Acting Sr. Resident Inspector SSES Mr. K. Kerns, Pa. DEP bc: R..R. Boesch NUCSA1 R. J. McKeon GENA93 Chambliss '

NUCSA4

G."D. Miller"'= GENA62'

A. Dyszel GENA93 R. F. Saunders NUCSA4 D. L. Filchner GENA63 R. R. Sgarro GENA61 G. T. Jones GENA61 J. P. Spadaro GENA93 J. M Kenny GENA61 R. R. Wehry NUCSA4 J. M Kulick GENA93 Licensing Files GENA61 C. R. Lehmann GENA93 NR Files GENA62 RRS:rrshtah 50I8.RRS I/l2/99 I I:30 AM